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MCNP benchmark analyses of critical experiments for the Space Nuclear Thermal Propulsion program

Conference ·
OSTI ID:10160195
; ; ; ; ;  [1];  [2]; ;  [3]
  1. Brookhaven National Lab., Upton, NY (United States)
  2. Sandia National Labs., Albuquerque, NM (United States)
  3. Babcock and Wilcox Co., Lynchburg, VA (United States)

Benchmark analyses have been performed of Particle Bed Reactor (PBR) critical experiments (CX) using the MCNP radiation transport code. The experiments have been conducted at the Sandia National Laboratory reactor facility in support of the Space Nuclear Thermal Propulsion (SNTP) program. The test reactor is a nineteen element water moderated and reflected thermal system. A series of integral experiments have been carried out to test the capabilities of the radiation transport codes to predict the performance of PBR systems. MCNP was selected as the preferred radiation analysis tool for the benchmark experiments. Comparison between experimental and calculational results indicate very good agreement. This paper describes the analyses of benchmark experiments designed to quantify the accuracy of the MCNP radiation transport code for predicting the performance characteristics of PBR reactors.

Research Organization:
Brookhaven National Lab., Upton, NY (United States)
Sponsoring Organization:
USDOE, Washington, DC (United States)
DOE Contract Number:
AC02-76CH00016
OSTI ID:
10160195
Report Number(s):
BNL--48698; CONF-930103--38; ON: DE93014046
Country of Publication:
United States
Language:
English